ML20161A091

From kanterella
Jump to navigation Jump to search
Proposed TS - CoC 1040 A4 App B
ML20161A091
Person / Time
Site: HI-STORM 100
Issue date: 10/26/2020
From:
Office of Nuclear Material Safety and Safeguards
To:
Holtec
CJJacobs NMSS/DFM/STL 415.6825
Shared Package
ML20161A087 List:
References
Download: ML20161A091 (56)
v • d • e


Text

CERTIFICATE OF COMPLIANCE NO. 1040 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM UMAX CANISTER STORAGE SYSTEM

TABLE OF CONTENTS 1.0 DEFINITIONS ........................................................................................................ 1-1 2.0 APPROVED CONTENTS ...................................................................................... 2-1 2.1 Fuel Specifications and loading conditions ........................................................ 2-1 2.2 Violations ........................................................................................................... 2-1 2.3 Decay Heat Limits ........................................................................................... 2-15 Table 2.1-1 Fuel Assembly Limits .......................................................................... 2-2 Table 2.1-2 PWR Fuel Assembly Characteristics .................................................. 2-6 Table 2.1-3 BWR Fuel Assembly Characteristics .................................................. 2-9 Table 2.1-4 Classification of Fuel Assembly for MPC-37 in the HI-STORM UMAX System ...................................................................................................... 2-14 Table 2.3-1 Permissible Heat Load for long term storage .................................... 2-16 Table 2.3-2 HI-STORM UMAX MPC-37 Type 1 Permissible Heat Loads ............ 2-19 Figure 2.3-1 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Short and Standard Fuel ........................................ 2-21 Figure 2.3-2 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-Term Storage for Short and Standard Fuel ....................................... 2-22 Figure 2.3-3 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Short Fuel .............................................................. 2-23 Figure 2.3-4 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Standard Fuel ........................................................ 2-24 Figure 2.3-5 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Long Fuel ............................................................... 2-25 Figure 2.3-6 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-term Storage for Long Fuel ............................................................... 2-26 Figure 2.3-7 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Long Fuel ............................................................... 2-27 Figure 2.3-8 HI-STORM UMAX MPC-37 Permissible Heat Load for Short and Standard Fuel for Helium Backfill Option3 in Table 3-2 of Appendix A ....................................................................................... 2-28 Figure 2.3-9 HI-STORM UMAX MPC-37 Permissible Heat Load for Long Fuel for Helium Backfill Option 3 in Table 3-2 of Appendix A ......................... 2-29 Figure 2.3-10 HI-STORM UMAX MPC-89 Permissible Heat Load for Long-Term Storage ............................................................................................ 2-30 Figure 2.3-11 HI-STORM UMAX MPC-89 Permissible Heat Load for Helium Backfill Option 2 in Table 3-2 of Appendix A ................................................ 2-31 Figure 2.3-12 HI-STORM UMAX MPC-37 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option Certificate of Compliance No. 1040 Amendment No. 4 Appendix B i

3 in Table 3-2 of Appendix A............................................................. 2-32 Figure 2.3-13 HI-STORM UMAX MPC-89 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option 2 in Table 3-2 of Appendix A............................................................. 2-33 Figure 2.3-14 HI-STORM UMAX MPC-37 Permissible Heat Load for 16x16A Undamaged Fuel with up to Thirty-seven DFCs ............................... 2-34 Figure 2.3-15: HI-STORM UMAX MPC-37 Type 1 Heat Permissible Heat Loads ...... 2-35 3.0 DESIGN FEATURES ............................................................................................. 3-1 3.1 Site .................................................................................................................... 3-1 3.2 Design Features Important for Criticality Control ............................................... 3-1 3.3 Codes and Standards ........................................................................................ 3-2 3.4 Site Specific Parameters and Analyses ........................................................... 3-10 3.5 Combustible Gas Monitoring During MPC Lid Welding and Cutting ................ 3-16 3.6 Periodic Corrosion Inspections for Underground Systems .............................. 3-16 Figure 3-1 SUBGRADE AND UNDERGRADE SPACE NOMENCLATURE....3-15 Table 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs) .... 3-3 Table 3-2 REFERENCE ASME CODE PARAGRAPHS FOR HI-STORM UMAX OVERPACK and HI-TRAC VW TRANSFER CASK, PRIMARY LOAD BEARING PARTS .................................................................................. 3-8 Table 3-3 LOAD COMBINATIONS FOR THE TOP SURFACE PAD, ISFSI PAD, AND SUPPORT FOUNDATION PAD PER ACI-318 (2005) ................. 3-12 Table 3-4 Values of Principal Design Parameters for the Underground ISFSI ...... 3-13 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B ii

Definitions 1.0 1.0 Definitions Refer to Appendix A for Definitions.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 1-1

Approved Contents 2.0 2.0 APPROVED CONTENTS 2.1 Fuel Specifications and Loading Conditions 2.1.1 Fuel to Be Stored in the HI-STORM UMAX Canister Storage System

a. UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, FUEL DEBRIS, and NON-FUEL HARDWARE meeting the limits specified in Table 2.1-1 and other referenced tables may be stored in the HI-STORM UMAX Canister Storage System.
b. All BWR fuel assemblies may be stored with or without ZR channels.

2.1.2 Fuel Loading Figures 2.3-1 through 2.3-7 and 2.3-10 define the unique cell numbers for the MPC-37 and MPC-89 models, respectively, and the maximum allowable heat load per fuel assembly for each cell under multiple loading conditions. Fuel assembly decay heat limits are specified in Section 2.3.1.

Fuel assemblies shall meet all other applicable limits specified in Tables 2.1-1 through 2.1-3.

2.2 Violations If any Fuel Specifications or Loading Conditions of 2.1 are violated, the following actions shall be completed:

2.2.1 The affected fuel assemblies shall be placed in a safe condition.

2.2.2 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the NRC Operations Center.

2.2.3 Within 30 days, submit a special report which describes the cause of the violation, and actions taken to restore compliance and prevent recurrence.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-1

Approved Contents 2.0 Table 2.1-1 (page 1 of 4)

Fuel Assembly Limits I. MPC MODEL: MPC-37 A. Allowable Contents

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and/or FUEL DEBRIS meeting the criteria in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
a. Cladding Type: ZR
b. Maximum Initial Enrichment: 5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1
c. Post-irradiation Cooling Time Cooling Time 3 years and Average Burnup Per Assembly Average Burnup 68.2 GWD/MTU Assembly:
d. Decay Heat Per Fuel Storage As specified in Section 2.3 Location:
e. Fuel Assembly Length: 199.2 inches (nominal design including NON-FUEL HARDWARE and DFC)
f. Fuel Assembly Width: 8.54 inches (nominal design)
g. Fuel Assembly Weight: 2050 lbs (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-2

Approved Contents 2.0 Table 2.1-1 (page 2 of 4)

Fuel Assembly Limits I. MPC MODEL: MPC-37 (continued)

B. Quantity per MPC: 37 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 1, 3, 4, 8, 9, 15, 23, 29, 30, 34, 35, and 37 (see Figures 2.3-1 through 2.3-7). The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

OR 37 class 16x16A UNDAMAGED FUEL ASSEMBLIES, with up to thirty-seven (37) of these stored in DAMAGED FUEL CONTAINERS, with up to twelve (12)

DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS stored in DAMAGED FUEL CONTAINERS (DFCs). DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS may be stored in fuel storage locations to 1, 3, 4, 8, 9, 15, 23, 29, 30, 34, 35, and 37 (see Figure 2.3-14). UNDAMAGED FUEL ASSEMBLIES, class 16x16A may be stored in DFCs only under loading pattern shown in Figure 2.3.14 OR For MPC-37 Type 1 only, up to 37 PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications under loading pattern shown in Figure 2.3.15 C. One (1) Neutron Source Assembly (NSA) is authorized for loading in the MPC-37.

D. Up to thirty (30) BRPAs are authorized for loading in the MPC-37.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs, RCCAs, CEAs, CRAs, or NSAs may only be loaded in fuel storage locations 5 through 7, 10 through 14, 17 through 21, 24 through 28, and 31 through 33 (see Figures 2.3-1 through 2.3-7).

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-3

Approved Contents 2.0 Table 2.1-1 (page 3 of 4)

Fuel Assembly Limits II. MPC MODEL: MPC-89 A. Allowable Contents

1. Uranium oxide BWR UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and/or FUEL DEBRIS meeting the criteria in Table 2.1-3, with or without channels and meeting the following specifications:
a. Cladding Type: ZR
b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the INITIAL ENRICHMENT(Note 1): applicable fuel assembly array/class.
c. Initial Maximum Rod Enrichment 5.0 wt. % U-235
d. Post-irradiation Cooling Time and Average Burnup Per Assembly
i. Array/Class 8x8F Cooling time 10 years and an assembly average burnup 27.5 GWD/MTU.

ii. All Other Array Classes Cooling Time 3 years and an assembly average burnup 65 GWD/MTU

e. Decay Heat Per Assembly
i. Array/Class 8x8F 183.5 Watts ii. All Other Array Classes As specified in Section 2.3
f. Fuel Assembly Length 176.5 inches (nominal design)
g. Fuel Assembly Width 5.95 inches (nominal design)
h. Fuel Assembly Weight 850 lbs, including a DFC as well as a channel Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-4

Approved Contents 2.0 Table 2.1-1 (page 4 of 4)

Fuel Assembly Limits II. MPC MODEL: MPC-89 (continued)

B. Quantity per MPC: 89 FUEL ASSEMBLIES with up to sixteen (16) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 1, 3, 4, 10, 11, 19, 29, 39, 51, 61, 71, 79, 80, 86, 87, and 89 (see Figure 2.3-10). The remaining fuel storage locations may be filled with BWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

Note 1: The lowest maximum allowable enrichment of any fuel assembly loaded in an MPC-89, based on fuel array class and fuel classification, is the maximum allowable enrichment for the remainder of the assemblies loaded in that MPC.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-5

Approved Contents 2.0 Table 2.1-2 (page 1 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 14x14 A 14x14 B 14x14 C 15x15 B 15x15 C Array/ Class No. of Fuel Rod 179 179 176 204 204 Locations Fuel Clad O.D. (in.) 0.400 0.417 0.440 0.420 0.417 Fuel Clad I.D. (in.) 0.3514 0.3734 0.3880 0.3736 0.3640 Fuel Pellet Dia. (in.)

0.3444 0.3659 0.3805 0.3671 0.3570 (Note 3)

Fuel Rod Pitch (in.) 0.556 0.556 0.580 0.563 0.563 Active Fuel Length 150 150 150 150 150 (in.)

No. of Guide and/or 5 17 17 21 21 Instrument Tubes (Note 2)

Guide/Instrument 0.017 0.017 0.038 0.015 0.0165 Tube Thickness (in.)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-6

Approved Contents 2.0 Table 2.1-2 (page 2 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 15x15 D 15x15 E 15x15 F 15x15 H 15x15 I Array/Class No. of Fuel Rod 216 (Note 208 208 208 208 Locations 4)

Fuel Clad O.D. (in.) 0.430 0.428 0.428 0.414 0.413 Fuel Clad I.D. (in.) 0.3800 0.3790 0.3820 0.3700 0.3670 Fuel Pellet Dia. (in.)

0.3735 0.3707 0.3742 0.3622 0.3600 (Note 3)

Fuel Rod Pitch (in.) 0.568 0.568 0.568 0.568 0.550 Active Fuel Length 150 150 150 150 150 (in.)

No. of Guide and/or 17 17 17 17 9 (Note 4)

Instrument Tubes Guide/Instrument 0.0150 0.0140 0.0140 0.0140 0.0140 Tube Thickness (in.)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-7

Approved Contents 2.0 Table 2.1-2 (page 3 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 16x16 A 16x16B 16x16C Array and Class No. of Fuel Rod 236 236 236 Locations Fuel Clad O.D. (in.) 0.382 0.374 0.374 Fuel Clad I.D. (in.) 0.3350 0.3290 0.3290 Fuel Pellet Dia. (in.)

0.3255 0.3225 0.3225 (Note 3)

Fuel Rod Pitch (in.) 0.506 0.506 0.485 Active Fuel length 150 150 150 (in.)

No. of Guide and/or 5 5 21 Instrument Tubes (Note 2) (Note 2)

Guide/Instrument 0.0350 0.04 0.0157 Tube Thickness (in.)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-8

Approved Contents 2.0 Table 2.1-2 (page 4 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 17x17A 17x17 B 17x17 C 17x17 D 17x17 E Array and Class No. of Fuel Rod 264 264 264 264 265 Locations Fuel Clad O.D. (in.) 0.360 0.372 0.377 0.372 0.372 Fuel Clad I.D. (in.) 0.3150 0.3310 0.3330 0.3310 0.3310 Fuel Pellet Dia. (in.)

0.3088 0.3232 0.3252 0.3232 0.3232 (Note 3)

Fuel Rod Pitch (in.) 0.496 0.496 0.502 0.496 0.496 Active Fuel length 150 150 150 170 170 (in.)

No. of Guide and/or 25 25 25 25 24 Instrument Tubes Guide/Instrument 0.016 0.014 0.020 0.014 0.014 Tube Thickness (in.)

Notes:

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. Each guide tube replaces four fuel rods.
3. Annular fuel pellets are allowed in the top and bottom 12 of the active fuel length.
4. Assemblies have one Instrument Tube and eight Guide Bars (Solid ZR). Some assemblies have up to 8 fuel rods removed or replaced by Guide Tubes.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-9

Approved Contents 2.0 Table 2.1-3 (page 1 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array 7x7 B 8x8 B 8x8 C 8x8 D 8x8 E and Class Maximum Planar-Average Initial

< 4.8 < 4.8 < 4.8 < 4.8 < 4.8 Enrichment (wt.%

235 U) (Note 14)

No. of Fuel Rod Locations (Full Length 49 63 or 64 62 60 or 61 59 or Total/Full Length)

Fuel Clad O.D. (in.) > 0.5630 > 0.4840 > 0.4830 > 0.4830 > 0.4930 Fuel Clad I.D. (in.) < 0.4990 < 0.4295 < 0.4250 < 0.4230 < 0.4250 Fuel Pellet Dia. (in.) < 0.4910 < 0.4195 < 0.4160 < 0.4140 < 0.4160 Fuel Rod Pitch (in.) < 0.738 < 0.642 < 0.641 < 0.640 < 0.640 Design Active Fuel

< 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods 1-4 0 1 or 0 2 5 (Note 10) (Note 6)

Water Rod Thickness N/A > 0.034 > 0.00 > 0.00 > 0.034 (in.)

Channel Thickness

< 0.120 < 0.120 < 0.120 < 0.120 < 0.100 (in.)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-10

Approved Contents 2.0 Table 2.1-3 (2 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 8x8F 9x9 A 9x9 B 9x9 C 9x9 D Array and Class Maximum Planar-Average Initial < 4.5

< 4.8 < 4.8 < 4.8 < 4.8 Enrichment (wt.% (Note 12) 235 U) (Note 14)

No. of Fuel Rod 74/66 64 72 80 79 Locations (Note 4)

Fuel Clad O.D. (in.) > 0.4576 > 0.4400 > 0.4330 > 0.4230 > 0.4240 Fuel Clad I.D. (in.) < 0.3996 < 0.3840 < 0.3810 < 0.3640 < 0.3640 Fuel Pellet Dia. (in.) < 0.3913 < 0.3760 < 0.3740 < 0.3565 < 0.3565 Fuel Rod Pitch (in.) < 0.609 < 0.566 < 0.572 < 0.572 < 0.572 Design Active Fuel

< 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods N/A 1 2 1 2 (Note 10) (Note 2) (Note 5)

Water Rod

> 0.0315 > 0.00 > 0.00 > 0.020 > 0.0300 Thickness (in.)

Channel Thickness

< 0.055 < 0.120 < 0.120 < 0.100 < 0.100 (in.)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-11

Approved Contents 2.0 Table 2.1-3 (page 3 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 9x9 E 9x9 F 9x9 G 10x10 A 10x10 B Array and Class (Note 2) (Note 2)

Maximum Planar-

< 4.5 < 4.5 Average Initial (Note (Note < 4.8 < 4.8 < 4.8 Enrichment (wt.%

235 12) 12)

U) (Note 14)

No. of Fuel Rod 92/78 91/83 76 76 72 Locations (Note 7) (Note 8)

Fuel Clad O.D. (in.) >0.4170 >0.4430 >0.4240 >0.4040 >0.3957 Fuel Clad I.D. (in.) <0.3640 <0.3860 <0.3640 < 0.3520 < 0.3480 Fuel Pellet Dia. (in.) <0.3530 <0.3745 <0.3565 < 0.3455 < 0.3420 Fuel Rod Pitch (in.) < 0.572 < 0.572 < 0.572 < 0.510 < 0.510 Design Active Fuel

< 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods 1 1 5 5 2 (Note 10) (Note 5) (Note 5)

Water Rod Thickness

>0.0120 >0.0120 >0.0320 >0.0300 > 0.00 (in.)

Channel Thickness

< 0.120 < 0.120 < 0.120 < 0.120 < 0.120 (in.)

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-12

Approved Contents 2.0 Table 2.1-3 (page 4 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and 10x10 C 10x10 F 10x10 G Class Maximum Planar-Average

< 4.7 < 4.6 Initial Enrichment (wt.% 235U) < 4.8 (Note 13) (Note 12)

(Note 14)

No. of Fuel Rod Locations 92/78 96 96/84 (Note 7)

Fuel Clad O.D. (in.) > 0.3780 > 0.4035 > 0.387 Fuel Clad I.D. (in.) < 0.3294 < 0.3570 < 0.340 Fuel Pellet Dia. (in.) < 0.3224 < 0.3500 < 0.334 Fuel Rod Pitch (in.) < 0.488 < 0.510 < 0.512 Design Active Fuel Length (in.) < 150 < 150 < 150 No. of Water Rods (Note 10) 5 5 2

(Note 9) (Note 9)

Water Rod Thickness (in.) > 0.031 > 0.030 > 0.031 Channel Thickness (in.) < 0.055 < 0.120 < 0.060 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-13

Approved Contents

2.0 NOTES

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. This assembly is known as QUAD+. It has four rectangular water cross segments dividing the assembly into four quadrants.
3. For the SPC 9x9-5 fuel assembly, each fuel rod must meet either the 9x9E or the 9x9F set of limits or clad O.D., clad I.D., and pellet diameter.
4. This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.
5. Square, replacing nine fuel rods.
6. Variable.
7. This assembly contains 92 total fuel rods; 78 full length rods and 14 partial length rods.
8. This assembly class contains 91 total fuel rods; 83 full length rods and 8 partial length rods.
9. One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.
10. These rods may also be sealed at both ends and contain ZR material in lieu of water.
11. Not used.
12. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.0 wt.% U-235.
13. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.6 wt.% U-235.
14. In accordance with the definition of UNDAMAGED FUEL, certain assemblies may be limited to 3.3 wt.% U-235. When loading these fuel assemblies, all assemblies in the MPC are limited to 3.3 wt.% U-235.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-14

Approved Contents 2.0 Table 2.1-4 CLASSIFICATION OF FUEL ASSEMBLY FOR MPC-37 IN THE HI-STORM UMAX ISFSI MPC Type Classification Nominal Active Fuel Length Short Fuel 128 inches < L < 144 inches MPC-37 Standard Fuel 144 inches < L < 168 inches Long Fuel L > 168 inches Note 1: L means "nominal active fuel length".

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-15

Approved Contents 2.0 2.3 Decay Heat Limits This section provides the limits on fuel assembly decay heat for storage in the HI-STORM UMAX Canister Storage System. The method to verify compliance, including examples, is provided in Chapter 13 of the HI-STORM UMAX FSAR.

2.3.1 Fuel Loading Decay Heat Limits Table 2.3-1 provides the maximum permissible decay heat under long-term storage for MPC-37 and MPC-89. Table 2.3-1 also lists the applicable figures providing the permissible decay heat per fuel storage location, including MPCs using the optional helium backfill pressure ranges permitted in Table 3-2 of Appendix A.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-16

Approved Contents 2.0 TABLE 2.3-1 PERMISSIBLE HEAT LOAD FOR LONG-TERM STORAGE Permissible Helium Backfill Permissible Heat Load Aggregate Heat MPC Type Pressure Option Heat Load Per Chart Load, kW (Notes 1,2) Storage Cell (Note 4) 1 1 Figure 2.3-1 33.88 Short Fuel 2 2 Figure 2.3-2 33.70 (Note 3) 3 1 Figure 2.3-3 33.53 Standard 1 1 Figure 2.3-1 33.88 Fuel 2 2 Figure 2.3-2 33.70 (Note 3 and

7) 3 1 Figure 2.3-4 35.30 1 1 Figure 2.3-5 35.76 Long Fuel 2 2 Figure 2.3-6 35.57 (Note 3)

MPC-37 3 1 Figure 2.3-7 37.06 Short Fuel 3 Figure 2.3-8 34.28 (Note 3) 3 Figure 2.3-12 33.46 Standard Fuel 3 Figure 2.3-8 34.28 (Note 3) 3 Figure 2.3-12 33.46 3 Figure 2.3-9 36.19 Long Fuel (Note 3) 3 Figure 2.3-12 33.46 16x16A Fuel with up to 32.3 3 Figure 2.3-14 37 DFCs (Note 6) (Note 5) 1 Figure 2.3-10 36.32 MPC-89 2 Figure 2.3-11 36.72 2 Figure 2.3-13 34.75 Notes:

1. For helium backfill pressure option pressure ranges see Appendix A, Table 3-2
2. For the details on the use of VDS to dry High Burnup Fuel see Appendix A, Table 3-1 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-17

Approved Contents 2.0

3. See Table 2.1-4 for fuel length data
4. Aggregate heat load is defined as the sum of heat loads of all stored fuel assemblies. The permissible aggregate heat load is set to 80% of the design basis heat load.
5. This aggregate heat load has been calculated with significant margin to fuel cladding limits, and is therefore not subject to the 80% penalty.
6. As stated in Table 2.1-1 Item I.B, this can include undamaged fuel both in DFCs and not, and damaged fuel in DFCs. These heat load limits apply with one or more undamaged fuel assemblies stored in DFCs.
7. For MPC-37 Type 1, the permissible Aggregate Heat Load is given in Table 2.3-2 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-18

Approved Contents 2.0 TABLE 2.3-2 HI-STORM UMAX MPC-37 TYPE 1 PERMISSIBLE HEAT LOADS Heat Load Permissible Helium Backfill Pressure Fuel Type (Note 1) per Storage Aggregate Heat Option (Note 2)

Cell Load (Note 3), kW Standard Fuel 1 Figure 2.3-15 32.3 Note 1: See Table 2.1-4 for fuel length data Note 2: For helium backfill pressure option pressure ranges see Appendix A, Table 3-2 Note 3: The aggregate heat load is defined as a sum of all stored fuel assemblies.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-19

Approved Contents 2.0 2.3.2 When complying with the maximum fuel storage location decay heat limits, users must account for the decay heat from both the fuel assembly and any NON-FUEL HARDWARE, as applicable for the particular fuel storage location, to ensure the decay heat emitted by all contents in a storage location does not exceed the limit.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-20

Approved Contents 2.0 1 2 3 0.873 0.873 0.873 4 5 6 7 8 0.873 1.602 1.602 1.602 0.873 9 10 11 12 13 14 15 0.873 1.602 1.017 1.017 1.017 1.602 0.873 16 17 18 19 20 21 22 0.873 1.602 1.017 1.017 1.017 1.602 0.873 23 24 25 26 27 28 29 0.873 1.602 1.017 1.017 1.017 1.602 0.873 30 31 32 33 34 0.873 1.602 1.602 1.602 0.873 35 36 37 0.873 0.873 0.873 Legend Cell ID Heat Load, kW Figure 2.3-1 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Short and Standard Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-21

Approved Contents 2.0 1 2 3 1.215 1.215 1.215 4 5 6 7 8 1.215 1.080 1.080 1.080 1.215 9 10 11 12 13 14 15 1.215 1.080 1.080 1.080 1.080 1.080 1.215 16 17 18 19 20 21 22 1.215 1.080 1.080 1.080 1.080 1.080 1.215 23 24 25 26 27 28 29 1.215 1.080 1.080 1.080 1.080 1.080 1.215 30 31 32 33 34 1.215 1.080 1.080 1.080 1.215 35 36 37 1.215 1.215 1.215 Legend Cell ID Heat Load, kW Figure 2.3-2 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-term Storage for Short and Standard Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-22

Approved Contents 2.0 1 2 3 0.922 0.922 0.922 4 5 6 7 8 0.922 1.520 1.520 1.520 0.922 9 10 11 12 13 14 15 0.922 1.710 0.950 0.950 0.950 1.710 0.922 16 17 18 19 20 21 22 0.922 1.520 0.950 0.570 0.950 1.520 0.922 23 24 25 26 27 28 29 0.922 1.710 0.950 0.950 0.950 1.710 0.922 30 31 32 33 34 0.922 1.520 1.520 1.520 0.922 35 36 37 0.922 0.922 0.922 Legend Cell ID Heat Load, kW Figure 2.3-3 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Short Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-23

Approved Contents 2.0 1 2 3 0.970 0.970 0.970 4 5 6 7 8 0.970 1.600 1.600 1.600 0.970 9 10 11 12 13 14 15 0.970 1.800 1.000 1.000 1.000 1.800 0.970 16 17 18 19 20 21 22 0.970 1.600 1.000 0.600 1.000 1.600 0.970 23 24 25 26 27 28 29 0.970 1.800 1.000 1.000 1.000 1.800 0.970 30 31 32 33 34 0.970 1.600 1.600 1.600 0.970 35 36 37 0.970 0.970 0.970 Legend Cell ID Heat Load, kW Figure 2.3-4 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Standard Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-24

Approved Contents 2.0 1 2 3 0.922 0.922 0.922 4 5 6 7 8 0.922 1.691 1.691 1.691 0.922 9 10 11 12 13 14 15 0.922 1.691 1.074 1.074 1.074 1.691 0.922 16 17 18 19 20 21 22 0.922 1.691 1.074 1.074 1.074 1.691 0.922 23 24 25 26 27 28 29 0.922 1.691 1.074 1.074 1.074 1.691 0.922 30 31 32 33 34 0.922 1.691 1.691 1.691 0.922 35 36 37 0.922 0.922 0.922 Legend Cell ID Heat Load, kW Figure 2.3-5 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Long Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-25

Approved Contents 2.0 1 2 3 1.283 1.283 1.283 4 5 6 7 8 1.283 1.140 1.140 1.140 1.283 9 10 11 12 13 14 15 1.283 1.140 1.140 1.140 1.140 1.140 1.283 16 17 18 19 20 21 22 1.283 1.140 1.140 1.140 1.140 1.140 1.283 23 24 25 26 27 28 29 1.283 1.140 1.140 1.140 1.140 1.140 1.283 30 31 32 33 34 1.283 1.140 1.140 1.140 1.283 35 36 37 1.283 1.283 1.283 Legend Cell ID Heat Load, kW Figure 2.3-6 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-term Storage for Long Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-26

Approved Contents 2.0 1 2 3 1.019 1.019 1.019 4 5 6 7 8 1.019 1.680 1.680 1.680 1.019 9 10 11 12 13 14 15 1.019 1.890 1.050 1.050 1.050 1.890 1.019 16 17 18 19 20 21 22 1.019 1.680 1.050 0.630 1.050 1.680 1.019 23 24 25 26 27 28 29 1.019 1.890 1.050 1.050 1.050 1.890 1.019 30 31 32 33 34 1.019 1.680 1.680 1.680 1.019 35 36 37 1.019 1.019 1.019 Legend Cell ID Heat Load, kW Figure 2.3-7 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Long Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-27

Approved Contents 2.0 1 2 3 0.785 0.785 0.785 4 5 6 7 8 0.785 1.441 1.441 1.441 0.785 9 10 11 12 13 14 15 0.785 1.441 0.915 0.915 0.915 1.441 0.785 16 17 18 19 20 21 22 0.785 1.441 0.915 0.915 0.915 1.441 0.785 23 24 25 26 27 28 29 0.785 1.441 0.915 0.915 0.915 1.441 0.785 30 31 32 33 34 0.785 1.441 1.441 1.441 0.785 35 36 37 0.785 0.785 0.785 Legend Cell ID Heat Load, kW Figure 2.3-8 HI-STORM UMAX MPC-37 Permissible Heat Load for Short and Standard Fuel for Helium Backfill Option 3 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-28

Approved Contents 2.0 1 2 3 0.829 0.829 0.829 4 5 6 7 8 0.829 1.521 1.521 1.521 0.829 9 10 11 12 13 14 15 0.829 1.521 0.966 0.966 0.966 1.521 0.829 16 17 18 19 20 21 22 0.829 1.521 0.966 0.966 0.966 1.521 0.829 23 24 25 26 27 28 29 0.829 1.521 0.966 0.966 0.966 1.521 0.829 30 31 32 33 34 0.829 1.521 1.521 1.521 0.829 35 36 37 0.829 0.829 0.829 Legend Cell ID Heat Load, kW Figure 2.3-9 HI-STORM UMAX MPC-37 Permissible Heat Load for Long Fuel for Helium Backfill Option 3 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-29

Approved Contents 2.0 1 2 3 0.431 0.431 0.431 4 5 6 7 8 9 10 0.431 0.431 0.431 0.607 0.431 0.431 0.431 11 12 13 14 15 16 17 18 19 0.431 0.431 0.607 0.607 0.607 0.607 0.607 0.431 0.431 20 21 22 23 24 25 26 27 28 0.431 0.607 0.607 0.607 0.607 0.607 0.607 0.607 0.431 29 30 31 32 33 34 35 36 37 38 39 0.431 0.431 0.607 0.607 0.431 0.431 0.431 0.607 0.607 0.431 0.431 40 41 42 43 44 45 46 47 48 49 50 0.431 0.607 0.607 0.607 0.431 0.431 0.431 0.607 0.607 0.607 0.431 51 52 53 54 55 56 57 58 59 60 61 0.431 0.431 0.607 0.607 0.431 0.431 0.431 0.607 0.607 0.431 0.431 62 63 64 65 66 67 68 69 70 0.431 0.607 0.607 0.607 0.607 0.607 0.607 0.607 0.431 71 72 73 74 75 76 77 78 79 0.431 0.431 0.607 0.607 0.607 0.607 0.607 0.431 0.431 80 81 82 83 84 85 86 0.431 0.431 0.431 0.607 0.431 0.431 0.431 87 88 89 0.431 0.431 0.431 Legend Figure 2.3-10 Cell ID HI-STORM UMAX MPC-89 Permissible Heat Load for Long-Term Storage Heat Load, kW Note that this figure shows the per cell heat load limit for storage.

The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-30

Approved Contents 2.0 1 2 3 0.387 0.387 0.387 4 5 6 7 8 9 10 0.387 0.387 0.387 0.546 0.387 0.387 0.387 11 12 13 14 15 16 17 18 19 0.387 0.387 0.546 0.546 0.546 0.546 0.546 0.387 0.387 20 21 22 23 24 25 26 27 28 0.387 0.546 0.546 0.546 0.546 0.546 0.546 0.546 0.387 29 30 31 32 33 34 35 36 37 38 39 0.387 0.387 0.546 0.546 0.387 0.387 0.387 0.546 0.546 0.387 0.387 40 41 42 43 44 45 46 47 48 49 50 0.387 0.546 0.546 0.546 0.387 0.387 0.387 0.546 0.546 0.546 0.387 51 52 53 54 55 56 57 58 59 60 61 0.387 0.387 0.546 0.546 0.387 0.387 0.387 0.546 0.546 0.387 0.387 62 63 64 65 66 67 68 69 70 0.387 0.546 0.546 0.546 0.546 0.546 0.546 0.546 0.387 71 72 73 74 75 76 77 78 79 0.387 0.387 0.546 0.546 0.546 0.546 0.546 0.387 0.387 80 81 82 83 84 85 86 0.387 0.387 0.387 0.546 0.387 0.387 0.387 87 88 89 0.387 0.387 0.387 Legend Figure 2.3-11 HI-STORM UMAX MPC-89 Permissible Heat Load for Helium Backfill Cell ID Option 2 in Table 3-2 of Appendix A Heat Load, kW Note that this figure shows the per cell heat load limit for storage.

The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-31

Approved Contents 2.0 1 2 3 0.97 0.97 0.97 4 5 6 7 8 0.97 0.97 0.97 0.97 0.97 9 10 11 12 13 14 15 0.97 0.97 0.7 0.7 0.7 0.97 0.97 16 17 18 19 20 21 22 0.97 0.97 0.7 0.7 0.7 0.97 0.97 23 24 25 26 27 28 29 0.97 0.97 0.7 0.7 0.7 0.97 0.97 30 31 32 33 34 0.97 0.97 0.97 0.97 0.97 35 36 37 0.97 0.97 0.97 Legend Cell ID Heat Load, kW Figure 2.3-12 HI-STORM UMAX MPC-37 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option 3 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-32

Approved Contents 2.0 1 2 3 0.44 0.44 0.44 4 5 6 7 8 9 10 0.44 0.44 0.44 0.35 0.44 0.44 0.44 11 12 13 14 15 16 17 18 19 0.44 0.44 0.35 0.35 0.35 0.35 0.35 0.44 0.44 20 21 22 23 24 25 26 27 28 0.44 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.44 29 30 31 32 33 34 35 36 37 38 39 0.44 0.44 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.44 0.44 40 41 42 43 44 45 46 47 48 49 50 0.44 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.44 51 52 53 54 55 56 57 58 59 60 61 0.44 0.44 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.44 0.44 62 63 64 65 66 67 68 69 70 0.44 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.44 71 72 73 74 75 76 77 78 79 0.44 0.44 0.35 0.35 0.35 0.35 0.35 0.44 0.44 80 81 82 83 84 85 86 0.44 0.44 0.44 0.35 0.44 0.44 0.44 87 88 89 0.44 0.44 0.44 Legend Figure 2.3-13 Cell ID HI-STORM UMAX MPC-89 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Heat Load, kW Option 2 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage.

The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-33

Approved Contents 2.0 1 2 3 0.80 0.80 0.80 4 5 6 7 8 1.00 1.00 1.40 1.00 1.00 9 10 11 12 13 14 15 0.80 1.00 0.60 0.60 0.60 1.00 0.80 16 17 18 19 20 21 22 0.80 1.40 0.60 0.30 0.60 1.40 0.80 23 24 25 26 27 28 29 0.80 1.00 0.60 0.60 0.60 1.00 0.80 30 31 32 33 34 1.00 1.00 1.40 1.00 1.00 35 36 37 0.80 0.80 0.80 Legend Cell ID Heat Load, kW Figure 2.3-14 HI-STORM UMAX MPC-37 Permissible Heat Load for 16x16A Undamaged Fuel with up to Thirty-seven DFCs Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-34

Approved Contents 2.0 0.725 0.865 0.725 0.66 1.075 1.24 1.075 0.66 0.725 1.075 0.775 0.865 0.775 1.075 0.725 0.865 1.24 0.865 0.285 0.865 1.24 0.865 0.725 1.075 0.775 0.865 0.775 1.075 0.725 0.66 1.075 1.24 1.075 0.66 0.725 0.865 0.725 Figure 2.3-15: HI-STORM UMAX MPC-37 Type 1 Heat Permissible Heat Loads (All storage cell heat loads are in kW)

Note that this figure shows the per cell heat load limit for storage. The permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-2 for corresponding permissible aggregate heat load and the helium backfill option.

Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-35

Design Features 3.0 3.0 DESIGN FEATURES 3.1 Site 3.1.1 Site Location The HI-STORM UMAX Canister Storage System is authorized for general use by 10 CFR Part 50 license holders at various site locations under the provisions of 10 CFR 72, Subpart K.

3.2 Design Features Important for Criticality Control 3.2.1 MPC-37

1. Basket cell ID: 8.92 in. (min. nominal)
2. Basket cell wall thickness: 0.57 in. (min.nominal )
3. B4C in the Metamic-HT: 10.0 wt % (min. nominal) 3.2.2 MPC-89
1. Basket cell ID: 5.99 in. (min.nominal)
2. Basket cell wall thickness: 0.38 in. (min.nominal)
3. B4C in the Metamic-HT: 10.0 wt % (min. nominal) 3.2.3 Metamic-HT Test Requirements
1. The weight percentage of the boron carbide must be confirmed to be greater than or equal to 10% in each lot of Al/ B4C powder.
2. The areal density of the B-10 isotope corresponding to the 10%

min. weight density in the manufactured Metamic HT panels shall be independently confirmed by the neutron attenuation test method by testing at least one coupon from a randomly selected panel in each lot.

3. If the B- 10 areal density criterion in the tested panel fails to meet the specified minimum, then the manufacturer has the option to reject the entire lot or to test a statistically significant number of panels and perform statistical analysis to show that the minimum areal density in the panels (that comprise the lot) is satisfied with 95% confidence.
4. All test procedures used in demonstrating compliance with the above requirements shall conform to the cask designer's QA program which has been approved by the USNRC under docket number 71-0784.

3.3 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2007, is the governing Code for the HI-STORM UMAX system MPC as clarified in Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-1

Design Features 3.0 Specification 3.3.1 below, except for Code Sections V and IX. However, the HI-STORM UMAX VVM is structurally qualified per the newer 2010 ASME code. The ASME Code paragraphs applicable to the manufacturing of HI-STORM UMAX VVM and transfer cask are listed in Table 3-2. The latest effective editions of ASME Code Sections V and IX, including addenda, may be used for activities governed by those sections, provided a written reconciliation of the later edition against the applicable edition (including addenda) specified above, is performed by the certificate holder. American Concrete Institute ACI-318 (2005) is the governing Code for both plain concrete and reinforced concrete as clarified in Chapter 3 of the Final Safety Analysis Report for the HI-STORM 100 UMAX System.

3.3.1 Alternatives to Codes, Standards, and Criteria Table 3-1 lists approved alternatives to the ASME Code for the design of the MPCs of the HI-STORM UMAX Canister Storage System.

3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria Proposed alternatives to the ASME Code,Section III, 2007 Edition, including modifications to the alternatives allowed by Specification 3.3.1 may be used on a case-specific basis when authorized by the Director of the Office of Nuclear Material Safety and Safeguards or designee. The request for such alternative should demonstrate that:

1. The proposed alternatives would provide an acceptable level of quality and safety, or
2. Compliance with the specified requirements of the ASME Code,Section III, 2007 Edition, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Requests for alternatives shall be submitted in accordance with 10 CFR 72.4.

(continued)

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-2

Design Features 3.0 3.0 DESIGN FEATURES (continued)

TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Subsection General Requirements. Because the MPC is not an ASME Enclosure NCA Requires preparation of a Code stamped vessel, none of the Vessel Design Specification, specifications, reports, certificates, or Design Report, other general requirements specified by Overpressure Protection NCA are required. In lieu of a Design Report, Certification of Specification and Design Report, the Construction Report, Data HI-STORM FSAR includes the design Report, and other criteria, service conditions, and load administrative controls for combinations for the design and an ASME Code stamped operation of the MPCs as well as the vessel. results of the stress analyses to demonstrate that applicable Code stress limits are met. Additionally, the fabricator is not required to have an ASME-certified QA program. All important-to-safety activities are governed by the NRC-approved Holtec QA program.

Because the cask components are not certified to the Code, the terms Certificate Holder and Inspector are not germane to the manufacturing of NRC-certified cask components. To eliminate ambiguity, the responsibilities assigned to the Certificate Holder in the Code, as applicable, shall be interpreted to apply to the NRC Certificate of Compliance (CoC) holder (and by extension, to the component fabricator) if the requirement must be fulfilled. The Code term Inspector means the QA/QC personnel of the CoC holder and its vendors assigned to oversee and inspect the manufacturing process.

MPC NB-1100 Statement of requirements MPC Enclosure Vessel is designed and Enclosure for Code stamping of will be fabricated in accordance with Vessel components. ASME Code,Section III, Subsection NB to the maximum practical extent, but Code stamping is not required.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-3

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC basket NB-1130 NB-1132.2(d) requires that The lugs that are used exclusively for supports the first connecting weld of lifting an empty MPC are welded to the and lift lugs a non-pressure retaining inside of the pressure-retaining MPC structural attachment to a shell, but are not designed in component shall be accordance with Subsection NB. The considered part of the lug-to-Enclosure Vessel Weld is component unless the weld required to meet the stress limits of is more than 2t from the Reg. Guide 3.61 in lieu of Subsection pressure retaining portion NB of the Code.

of the component, where t is the nominal thickness of the pressure retaining material.

NB-1132.2(e) requires that the first connecting weld of a welded nonstructural attachment to a component shall conform to NB-4430 if the connecting weld is within 2t from the pressure retaining portion of the component.

MPC NB-2000 Requires materials to be Materials will be supplied by Holtec Enclosure supplied by ASME- approved suppliers with Certified Vessel approved material supplier. Material Test Reports (CMTRs) in accordance with NB-2000 requirements.

MPC NB-3100 Provides requirements for These requirements are subsumed by Enclosure NF-3100 determining design loading the HI-STORM FW FSAR, serving as Vessel conditions, such as the Design Specification, which pressure, temperature, and establishes the service conditions and mechanical loads. load combinations for the storage system.

MPC NB-4120 NB-4121.2 and NF-4121.2 In-shop operations of short duration that Enclosure provide requirements for apply heat to a component, such as Vessel repetition of tensile or plasma cutting of plate stock, welding, impact tests for material machining, and coating are not, unless subjected to heat treatment explicitly stated by the Code, defined as during fabrication or heat treatment operations.

installation.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-4

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC NB-4220 Requires certain forming The cylindricity measurements on the Enclosure tolerances to be met for rolled shells are not specifically Vessel cylindrical, conical, or recorded in the shop travelers, as would spherical shells of a vessel. be the case for a Code-stamped pressure vessel. Rather, the requirements on inter-component clearances (such as the MPC-to-transfer cask) are guaranteed through fixture-controlled manufacturing. The fabrication specification and shop procedures ensure that all dimensional design objectives, including inter-component annular clearances are satisfied. The dimensions required to be met in fabrication are chosen to meet the functional requirements of the dry storage components. Thus, although the post-forming Code cylindricity requirements are not evaluated for compliance directly, they are indirectly satisfied (actually exceeded) in the final manufactured components.

MPC NB-4122 Implies that with the MPCs are built in lots. Material Enclosure exception of studs, bolts, traceability on raw materials to a heat Vessel nuts and heat exchanger number and corresponding CMTR is tubes, CMTRs must be maintained by Holtec through markings traceable to a specific on the raw material. Where material is piece of material in a cut or processed, markings are component. transferred accordingly to assure traceability. As materials are assembled into the lot of MPCs being manufactured, documentation is maintained to identify the heat numbers of materials being used for that item in the multiple MPCs being manufactured under that lot. A specific item within a specific MPC will have a number of heat numbers identified as possibly being used for the item in that particular MPC of which one or more of those heat numbers (and corresponding CMTRS) will have actually been used. All of the heat numbers identified will comply with the requirements for the particular item.

MPC Lid and NB-4243 Full penetration welds MPC lid and closure ring are not full Closure Ring required for Category C penetration welds. They are welded Welds Joints (flat head to main independently to provide a redundant shell per NB-3352.3) seal.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-5

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Closure NB-5230 Radiographic (RT) or Root (if more than one weld pass is Ring, Vent and ultrasonic (UT) required) and final liquid penetrant Drain Cover examination required. examination to be performed in Plate Welds accordance with NB-5245. The closure ring provides independent redundant closure for vent and drain cover plates.

Vent and drain port cover plate welds are helium leakage tested.

MPC Lid to NB-5230 Radiographic (RT) or Only progressive liquid penetrant (PT)

Shell Weld ultrasonic (UT) examination is permitted. PT examination required. examination will include the root and final weld layers and each approx. 3/8" of weld depth.

MPC NB-6111 All completed pressure The MPC vessel is welded in the field Enclosure retaining systems shall be following fuel assembly loading. After Vessel and Lid pressure tested. the lid to shell weld is completed, the MPC shall then be pressure tested as defined in Chapter 10. Accessibility for leakage inspections precludes a Code compliant pressure test. Since the shell welds of the MPC cannot be checked for leakage during this pressure test, the shop leakage test to 10-7 ref cc/sec provides reasonable assurance as to its leak tightness. All MPC enclosure vessel welds (except closure ring and vent/drain cover plate) are inspected by volumetric examination. The MPC lid-to-shell weld shall be verified by progressive PT examination. PT must include the root and final layers and each approximately 3/8 inch of weld depth.

The inspection results, including relevant findings (indications) shall be made a permanent part of the users records by video, photographic, of other means which provide an equivalent record of weld integrity. The video or photographic records should be taken during the final interpretation period described in ASME Section V, Article 6, T-676. The vent/drain cover plate and the closure ring welds are confirmed by liquid penetrant examination. The inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code Section III, NB-5350.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-6

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC NB-7000 Vessels are required to No overpressure protection is provided.

Enclosure have overpressure Function of MPC enclosure vessel is to Vessel protection. contain radioactive contents under normal, off-normal, and accident conditions of storage. MPC vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.

MPC NB-8000 States requirements for The HI-STORM UMAX system is to be Enclosure nameplates, stamping and marked and identified in accordance Vessel reports per NCA-8000. with 10CFR71 and 10CFR72 requirements. Code stamping is not required. QA data package to be in accordance with Holtec approved QA program.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-7

Design Features 3.0 Table 3-2 REFERENCE ASME CODE PARAGRAPHS FOR VVM PRIMARY LOAD BEARING PARTS Item Code Explanation and Applicability Paragraph

[2.6.1]

1. Definition of primary and NF-1215 -

secondary members

2. Jurisdictional boundary NF-1133 The VVMs jurisdictional boundary is defined by the bottom surface of the SFP, the top surface of the ISFSI pad and the SES side surfaces.
3. Certification of NF-2130(b) and Materials shall be certified to material(structural) (c) the applicable Section II of the ASME Code or equivalent ASTM Specification.
4. Heat treatment of material NF-2170 and -

NF-2180

5. Storage of welding material NF-2400 -
6. Welding procedure Section IX -
7. Welding material Section II -
8. Loading conditions NF-3111 -
9. Allowable stress values NF-3112.3 -
10. Rolling and sliding NF-3424 -

supports

11. Differential thermal NF-3127 -

expansion

12. Stress analysis NF-3143 Provisions for stress analysis NF-3380 for Class 3 plate and shell NF-3522 supports and for linear supports NF-3523 are applicable for Closure Lid and Container Shell, respectively.
13. Cutting of plate stock NF-4211 -

NF-4211.1

14. Forming NF-4212 -
15. Forming tolerance NF-4221 Applies to the Container Shell
16. Fitting and Aligning Tack NF-4231 -

Welds NF-4231.1

17. Alignment NF-4232 -
18. Storage of Welding NF-4411 -

Materials

19. Cleanliness of Weld NF-4412 Applies to structural and non-Surfaces structural welds Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-8

Design Features 3.0 Table 3-2 REFERENCE ASME CODE PARAGRAPHS FOR VVM PRIMARY LOAD BEARING PARTS Item Code Explanation and Applicability Paragraph

[2.6.1]

20. Backing Strips, Peening NF-4421 Applies to structural and non-NF-4422 structural welds
21. Pre-heating and Interpass NF-4611 Applies to structural and non-Temperature NF-4612 structural welds NF-4613
22. Non-Destructive NF-5360 InvokesSection V Examination
23. NDE Personnel NF-5522 -

Certification NF-5523 NF-5530 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-9

Design Features 3.0 3.0 DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the system user are, as a minimum, as follows:

1. The temperature of 80o F is the maximum average yearly temperature.
2. The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40o F and less than 125o F.
3. The resultant zero period acceleration at the top of the grade and at the elevation of the Support Foundation Pad (SFP) at the host site (computed by the Newmarks rule as the sum of A+0.4*B+0.4*C, where A, B, C denote the free field ZPAs in the three orthogonal directions in decreasing magnitude, i.e., A B C) shall be less than or equal to 1.3 and 1.214, respectively.

For HI-STORM UMAX Version MSE, the corresponding Newmark sum of the ZPAs at the top of the Support Foundation Pad is limited to 2.121 Gs and the vertical ZPA is limited to 1.0G.

4. The analyzed flood condition of 15 fps water velocity and a height of 125 feet of water (full submergence of the loaded cask) are not exceeded.
5. The potential for fire and explosion shall be based on site-specific considerations. The user shall demonstrate that the site-specific potential for fire is bounded by the fire conditions analyzed by the Certificate Holder, or an analysis of the site-specific fire considerations shall be performed.
6. The moment and shear capacities of the ISFSI Structures shall meet the structural requirements under the load combinations in Table 3-3.
7. Radiation Protection Space (RPS) as defined in Subsection 5.3.9 of Appendix A, is intended to ensure that the subgrade material in and around the lateral space occupied by the VVMs remains essentially intact under all service conditions including during an excavation activity adjacent to the RPS.
8. The SFP for a VVM array established in any one construction campaign shall be of monolithic construction, to the extent practicable, to maximize the physical stability of the underground installation.
9. Excavation activities contiguous to a loaded UMAX ISFSI on the side facing the excavation can occur down to the depth of the bottom surface of the SFP of the loaded ISFSI (i.e. within the area labeled Space B in Figure 3-
1) considering that there may be minor variations in the depth due to normal construction practices. For excavation activities which are contiguous to the loaded ISFSI (within a distance W, see Figure 3-1) and below the depth of the bottom surface of the SFP (i.e. within the area labeled Space D in Figure 3-1), asite-specific seismic analysis will be performed to demonstrate the stability of the RPS boundary and structural integrity of the ISFSI structure. This analysis shall be submitted to Holtec International to be incorporated in an amendment request for NRC review and approval Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-10

Design Features 3.0 prior to any excavation taking place.

10. In cases where engineered features (i.e., berms and shield walls) are used to ensure that the requirements of 10CFR72.104(a) are met, such features are to be considered important-to-safety and must be evaluated to determine the applicable quality assurance category.
11. LOADING OPERATIONS, TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area Ambient Temperature 0o F.
12. For those users whose site-specific design basis includes an event or events (e.g., flood) that result in the blockage of any VVM inlet or outlet air ducts for an extended period of time (i.e., longer than the total Completion Time of LCO 3.1.2), an analysis or evaluation may be performed to demonstrate adequate heat removal is available for the duration of the event. Adequate heat removal is defined as fuel cladding temperatures remaining below the short term temperature limit. If the analysis or evaluation is not performed, or if fuel cladding temperature limits are unable to be demonstrated by analysis or evaluation to remain below the short term temperature limit for the duration of the event, provisions shall be established to provide alternate means of cooling to accomplish this objective.
13. Users shall establish procedural and/or mechanical barriers to ensure that during LOADING OPERATIONS and UNLOADING OPERATIONS, either the fuel cladding is covered by water, or the MPC is filled with an inert gas.
14. The entire haul route shall be evaluated to ensure that the route can support the weight of the loaded transfer cask and its conveyance.
15. The loaded transfer cask and its conveyance shall be evaluated to ensure, under the site specific Design Basis Earthquake, that the cask and its conveyance does not tipover or slide off the haul route.

(continued)

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-11

Design Features 3.0 DESIGN FEATURES (continued)

Table 3-3 LOAD COMBINATIONS FOR THE TOP SURFACE PAD, ISFSI PAD, AND SUPPORT FOUNDATION PAD PER ACI-318 (2005)

Load Combination Case Load Combination LC-1 1.4D LC-2 1.2D + 1.6L LC-3 1.2D + E + L where:

D: Dead Load including long-term differential settlement effects.

L: Live Load E: DBE for the Site Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-12

Design Features 3.0 DESIGN FEATURES (continued)

Table 3-4 Values of Principal Design Parameters for the Underground ISFSI Thickness of the Support Foundation Pad, 33 inch (nominal)

Thickness of the ISFSI Pad and curb, inch 34 (nominal)

Thickness of the ISFSI Pad, inch (nominal) 30 Rebar Size* and Layout* (nominal) #11 @ 9" each face, each direction Rebar Concrete Cover (top and bottom)*, inch per 7.7.1 of ACI-318 (2005)

Compressive Strength of Concrete at 28 4500 days*, psi Compressive Strength of Self-hardening 1,000 Engineered Subgrade (SES), psi For Version MSE only, the Compressive 3000 Strength of plain concrete, psi Lower Bound Shear Wave Velocity in the 1,300 Subgrade lateral to the VVM (Figure 3-1 Space A), fps**

Depth Averaged Density of subgrade in Space 120 A. (Figure 3-1)1 (lb/ft3)

Depth Averaged Density of subgrade in Space 110 B. (Figure 3-1)1 (lb/ft3)

Depth Averaged Density of subgrade in Space 120 C. (Figure 3-1)2 (lb/ft3)

Depth Averaged Density of subgrade in Space 120 D. (Figure 3-1)3 (lb/ft3)

Lower Bound Shear Wave Velocity in the 485 Subgrade below the Support Foundation Pad (Figure 3-1 Space C & D), fps**

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-13

Design Features 3.0 Lower Bound Shear Wave Velocity in the 450 Subgrade laterally surrounding the ISFSI (Figure 3-1 Space B), fps**

For Version MSE only, Nominal Strain compatible Shear wave Velocity in Space B, 344 fps

  • Applies to Support Foundation Pad and ISFSI Pad.
    • Strain compatible effective shear wave velocities shall be computed using the guidance provided in Section 16 of the International Building Code, 2009 Edition.

Users must account for potential variability in the subgrade shear wave velocity in accordance with Section 3.7.2 of NUREG-0800.

Notes:

1. A lower average density value may be used in shielding analysis per FSAR Chapter 5 for conservatism.
2. Not required for shielding, not credited in Version MSE model.
3. This space will typically contain native soil. Not required for shielding, not credited in Version MSE model.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-14

Design Features 3.0 Figure 3 SUBGRADE AND UNDERGRADE SPACE NOMENCLATURE Note: W is a representative dimension of the ISFSI determined by site-specific layouts Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-15

Design Features 3.0 3.0 DESIGN FEATURES (continued) 3.5 Combustible Gas Monitoring During MPC Lid Welding and Cutting During MPC lid-to-shell welding and cutting operations, combustible gas monitoring of the space under the MPC lid is required, to ensure that there is no combustible mixture present.

3.6 Periodic Corrosion Inspections for Underground Systems HI-STORM UMAX VVM ISFSIs not employing an impressed current cathodic protection system shall be subject to visual and UT inspection of at least one representative VVM to check for significant corrosion of the CEC Container Shell and Bottom Plate at an interval not to exceed 20 years. The VVM chosen for inspection is not required to be in use or to have previously contained a loaded MPC. The VVM considered to be most vulnerable to corrosion degradation shall be selected for inspection. If significant corrosion is identified, either an evaluation to demonstrate sufficient continued structural integrity (sufficient for at least the remainder of the licensing period) shall be performed or the affected VVM shall be promptly scheduled for repair or decommissioning. Through wall corrosion shall not be permitted without promptly scheduling for repair or decommissioning.

Promptness of repair or decommissioning shall be commensurate with the extent of degradation of the VVM but shall not exceed 3 years from the date of inspection.

If the representative VVM is determined to require repair or decommissioning, the next most vulnerable VVM shall be selected for inspection. This inspection process shall conclude when a VVM is found that does not require repair or decommissioning. Since the last VVM inspected is considered more prone to corrosion than the remaining un-inspected VVMs, the last VVM inspected becomes the representative VVM for the remaining VVMs.

Inspections Visual Inspection: Visual inspection of the inner surfaces of the CEC Container Shell and Bottom Plate for indications of significant or through wall corrosion (i.e.,

holes).

UT Inspection: The UT inspection or an equivalent method shall be used to measure CEC shell wall thickness to determine the extent of metal loss from corrosion. A minimum of 16 data points shall be obtained, 4 near the top, 4 near the mid-height and 4 near the bottom of the CEC Container Shell all approximately 0, 90, 180, and 270 degrees apart; and 4 on the CEC Bottom Plate near the CEC Container Shell approximately 0, 90, 180, and 270 degrees apart. Locations where visual inspection has identified potentially significant corrosion shall also receive UT inspection. Locations suspected of significant corrosion may receive further UT inspection to determine the extent of corrosion.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-16

Design Features 3.0 Inspection Criteria General wall thinning exceeding 1/8 in depth and local pitting exceeding 1/4" in depth are conditions of significant corrosion.

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-17

Retrieved from "https://kanterella.com/w/index.php?title=ML20161A091&oldid=3042542"